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A neutron detector for measurement of total neutron production cross sections

Abstract

A neutron detector has been constructed and calibrated for the accurate measurement of total neutron production cross sections. The detector consists of a polyethylene sphere of 60 cm diameter in which eight /sup 10/BF/sub 3/ counters have been installed radially. The relative efficiency of this detector has been determined for average neutron energies from 30 keV to 1.5 MeV by counting neutrons from /sup 7/Li(p, n)/sup 7/Be. By adjusting the radial positions of the BF/sub 3/ counters in the polyethylene sphere the efficiency for neutron detection was made nearly constant for this energy range. Measurement of absolute efficiency for the same neutron energy range has been done by counting the neutrons from /sup 51/V(p, n)/sup 51/Cr and /sup 57/Fe(p, n)/sup 57/Co reactions and determining the absolute number of residual nuclei produced during the measurement of neutron yield. Details of absolute efficiency measurements and the use of the detector for determination of neutron production cross sections are given.
Authors:
Sekharan, K K; Laumer, H; Kern, B D; Gabbard, F [1] 
  1. Kentucky Univ., Lexington (USA). Dept. of Physics and Astronomy
Publication Date:
Mar 01, 1976
Product Type:
Journal Article
Reference Number:
AIX-07-256358; ERA-02-007908; EDB-77-003529
Resource Relation:
Journal Name: Nucl. Instrum. Methods; (Netherlands); Journal Volume: 133:2
Subject:
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; BF3 COUNTERS; PERFORMANCE; NEUTRON DETECTION; CALIBRATION; EFFICIENCY; FOUR-PI COUNTING; KEV RANGE 10-100; KEV RANGE 100-1000; MEV RANGE 01-10; NUCLEAR REACTIONS; PARTICLE PRODUCTION; POLYETHYLENES; TOTAL CROSS SECTIONS; COUNTING TECHNIQUES; CROSS SECTIONS; ENERGY RANGE; INTERACTIONS; KEV RANGE; MEASURING INSTRUMENTS; MEV RANGE; NEUTRON DETECTORS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; PARTICLE INTERACTIONS; POLYMERS; POLYOLEFINS; PROPORTIONAL COUNTERS; RADIATION DETECTION; RADIATION DETECTORS; 440101* - Radiation Instrumentation- General Detectors or Monitors & Radiometric Instruments
OSTI ID:
7335652
Country of Origin:
Netherlands
Language:
English
Other Identifying Numbers:
Journal ID: CODEN: NUIMA
Submitting Site:
INIS
Size:
Pages: 253-257
Announcement Date:
Sep 01, 1976

Citation Formats

Sekharan, K K, Laumer, H, Kern, B D, and Gabbard, F. A neutron detector for measurement of total neutron production cross sections. Netherlands: N. p., 1976. Web. doi:10.1016/0029-554X(76)90617-0.
Sekharan, K K, Laumer, H, Kern, B D, & Gabbard, F. A neutron detector for measurement of total neutron production cross sections. Netherlands. doi:10.1016/0029-554X(76)90617-0.
Sekharan, K K, Laumer, H, Kern, B D, and Gabbard, F. 1976. "A neutron detector for measurement of total neutron production cross sections." Netherlands. doi:10.1016/0029-554X(76)90617-0. https://www.osti.gov/servlets/purl/10.1016/0029-554X(76)90617-0.
@misc{etde_7335652,
title = {A neutron detector for measurement of total neutron production cross sections}
author = {Sekharan, K K, Laumer, H, Kern, B D, and Gabbard, F}
abstractNote = {A neutron detector has been constructed and calibrated for the accurate measurement of total neutron production cross sections. The detector consists of a polyethylene sphere of 60 cm diameter in which eight /sup 10/BF/sub 3/ counters have been installed radially. The relative efficiency of this detector has been determined for average neutron energies from 30 keV to 1.5 MeV by counting neutrons from /sup 7/Li(p, n)/sup 7/Be. By adjusting the radial positions of the BF/sub 3/ counters in the polyethylene sphere the efficiency for neutron detection was made nearly constant for this energy range. Measurement of absolute efficiency for the same neutron energy range has been done by counting the neutrons from /sup 51/V(p, n)/sup 51/Cr and /sup 57/Fe(p, n)/sup 57/Co reactions and determining the absolute number of residual nuclei produced during the measurement of neutron yield. Details of absolute efficiency measurements and the use of the detector for determination of neutron production cross sections are given.}
doi = {10.1016/0029-554X(76)90617-0}
journal = {Nucl. Instrum. Methods; (Netherlands)}
volume = {133:2}
journal type = {AC}
place = {Netherlands}
year = {1976}
month = {Mar}
}